
Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF)
出版:American Society for Testing and Materials

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基本信息
标准编号: ASTM E900-02(2007)
发布时间:2007/7/15 0:00:00
标准类别:Standard
出版单位:American Society for Testing and Materials
标准页数:4
标准简介
CONTAINED IN VOL. 12.02, 2007Presents a method for predicting reference transition temperature adjustments for irradiated light-water cooled power reactor pressure vessel materials based on Charpy V-notch 41-J (30-ftlbf) data.
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